Title :
ANDREA recalculation of operation history of VVER-440
Author :
Heraltova, Lenka ; Frybort, Jan
Author_Institution :
Fac. of Nucl. Sci. & Phys. Eng., Czech Tech. Univ. in Prague, Prague, Czech Republic
Abstract :
Macrocode ANDREA has been developed in UJV Rez a.s. It is used for neutronic calculation of fuel batches. During its development, the code was verified and validated for reactors VVER-1000 and new version ANDREA 2.0 was validated also for VVER-440 reactors in year 2013. This paper describes process of validation of the ANDREA code for reactors VVER-440. Firstly, the new features implemented into the solver were tested by a simple benchmark, then a Full-Core benchmark for VVER-440 reactors was recalculated and finally real operational data from NPP Dukovany, Czech Republic were used to evaluate the ability to predict characteristics of fuel batches.
Keywords :
fission reactor core control; fission reactor fuel; light water reactors; nuclear engineering computing; AD 2013; ANDREA code; ANDREA recalculation; Czech Republic; Macrocode ANDREA; NPP Dukovany; VVER-1000 reactors; VVER-440 operation history; VVER-440 reactors; fuel batches; neutronic calculation; Assembly; Benchmark testing; Fuels; Inductors; Pins; Power distribution; Temperature measurement; ANDREA; VVER-440; benchmark;
Conference_Titel :
Electric Power Engineering (EPE), Proccedings of the 2014 15th International Scientific Conference on
Conference_Location :
Brno
DOI :
10.1109/EPE.2014.6839508
